Ion cyclotron range of frequencies heating and flow generation in deuterium{endash}tritium plasmas
- Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey08543 (United States)
- Oak Ridge National Laboratory, Oak Ridge, Tennessee37831-8071 (United States)
Recent radio-frequency heating experiments on the Tokamak Fusion Test Reactor (TFTR) [Hawryluk {ital et al.}, Plasma Phys. Controlled Fusion {bold 33}, 1509 (1991)] have focused on developing tools for both pressure and current profile control in deuterium{endash}tritium (DT) plasmas. A new antenna was added to investigate pressure profile control utilizing direct ion Bernstein wave (IBW) heating. This was the first time direct IBW heating was explored on TFTR. Plasma heating and driven poloidal flows are observed. Previously heating and current drive via mode-converted IBW waves had been demonstrated in non-DT plasmas but efforts in DT plasmas had been unsuccessful. This lack of success had been ascribed to the presence of a small {sup 7}Li minority ion population. In the most recent experiments {sup 6}Li was used exclusively for machine conditioning and mode-conversion heating consistent with theory is now observed in DT plasmas. {copyright} {ital 1998 American Institute of Physics.}
- OSTI ID:
- 627768
- Report Number(s):
- CONF-971103-; ISSN 1070-664X; TRN: 98:006120
- Journal Information:
- Physics of Plasmas, Vol. 5, Issue 5; Conference: 39. annual meeting of the Division of Plasma Physics of the American Physical Society, Pittsburgh, PA (United States), 17-21 Nov 1997; Other Information: PBD: May 1998
- Country of Publication:
- United States
- Language:
- English
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